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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
D. W. Jeppson, C. Savatteri
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1403-1408
Safety | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29539
Articles are hosted by Taylor and Francis Online.
A fusion safety experiment was conducted to determine the consequences of water injection into high-temperature lithium-lead alloy under postulated reactor accident conditions. The temperature and pressure response, fraction of water reacted, quantity of hydrogen produced, and behavior of radioactive species associated with the use of this alloy as a breeder material were determined. The reaction products were identified and the aerosol was characterized for particle size, chemical composition, and deposition rate. The water injection was shown to be self limiting for a blanket module designed to withstand the pressure of the water coolant. Radioactive doses associated with the aerosol release from a high-temperature alloy breeder module were determined to be several orders of magnitude below the dose limit for acute health effects. The results were compared to previous experiments and recommendations were made.
